U Uranium - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook U Uranium write by . This book was released on 2013-11-11. U Uranium available in PDF, EPUB and Kindle. The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.
U Uranium
U Uranium - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook U Uranium write by H. Holleck. This book was released on 2013-11-11. U Uranium available in PDF, EPUB and Kindle. The present volume Uranium C12 covers the binary and polynary carbides of uranium, including ternary carbides with nonmetals like the carbide oxides and carbide nitrides U(C,O) and U(C,N). The binary carbide UC and especially the mixed carbide (UO.80PUO.20)C are of special importance due to their potential as the fuel for advanced .. Fast Breeder Reactors" because of properties such as the short doubling time, the high fissionable material density, and the good thermal conductivity. On the other hand, the dicarbide UC is of interest for .. High 2 Temperature Reactors", especially in the form of the mixed carbide (U . Th . )C . For O80 o20 2 the first time, India used mixed uranium-plutonium carbide (U . PU .)C as the fuel for its O3 O7 own newly developed 15 MW Fast Breeder Reactor at Kalpakkam, south of Madras. el Because of the technological importance of the uranium carbides a lot of data were published only in reports. In most cases, it was the aim of these less-scientifically based studies to promote the carbide fuel development on an economical basis. The lack of analyti cal data on the purity of the samples, missing characterization of the present phases, etc., hQINever, does not allow the discussion of the results of such references in this handbook. Therefore, only reliable publications were cited. For the technical fabrication of uranium carbides and their irradiation behavior, see Volumes A3 and A4 of this Handbook.
Uranium
Uranium - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Uranium write by Tom Zoellner. This book was released on 2009. Uranium available in PDF, EPUB and Kindle. A history of the powerful mineral element explores its role as a virtually limitless energy source, its controversial applications as a healing tool and weapon, and the ways in which its reputation has been used to promote war agendas in the middle east.
U Uranium
U Uranium - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook U Uranium write by Helmut Holleck. This book was released on 1987. U Uranium available in PDF, EPUB and Kindle. The present volume Uranium C12 covers the binary and polynary carbides of uranium, including ternary carbides with nonmetals like the carbide oxides and carbide nitrides U(C,O) and U(C,N). The binary carbide UC and especially the mixed carbide (UO.80PUO.20)C are of special importance due to their potential as the fuel for advanced .. Fast Breeder Reactors" because of properties such as the short doubling time, the high fissionable material density, and the good thermal conductivity. On the other hand, the dicarbide UC is of interest for .. High 2 Temperature Reactors", especially in the form of the mixed carbide (U . Th . )C . For O80 o20 2 the first time, India used mixed uranium-plutonium carbide (U . PU .)C as the fuel for its O3 O7 own newly developed 15 MW Fast Breeder Reactor at Kalpakkam, south of Madras. el Because of the technological importance of the uranium carbides a lot of data were published only in reports. In most cases, it was the aim of these less-scientifically based studies to promote the carbide fuel development on an economical basis. The lack of analyti cal data on the purity of the samples, missing characterization of the present phases, etc., hQINever, does not allow the discussion of the results of such references in this handbook. Therefore, only reliable publications were cited. For the technical fabrication of uranium carbides and their irradiation behavior, see Volumes A3 and A4 of this Handbook.
Medical Isotope Production Without Highly Enriched Uranium
Medical Isotope Production Without Highly Enriched Uranium - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Medical Isotope Production Without Highly Enriched Uranium write by National Research Council. This book was released on 2009-06-27. Medical Isotope Production Without Highly Enriched Uranium available in PDF, EPUB and Kindle. This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.
